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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
DOE-NE leadership discuss nuclear in the FY 2025 budget request
Members of the Department of Energy Office of Nuclear Energy leadership team detailed the DOE's fiscal year 2025 Congressional budget request in a webinar hosted last week by the American Nuclear Society. The DOE’s FY 2025 budget request includes nearly $1.6 billion for the Office of Nuclear Energy. The webinar was sponsored by Paragon Energy Solutions; ANS members can view the recording online.
Hisashi Ninokata, Hideki Kamide
Nuclear Technology | Volume 181 | Number 1 | January 2013 | Pages 11-23
Technical Paper | Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) / Fission Reactors; Thermal Hydraulics | doi.org/10.13182/NT13-A15753
Articles are hosted by Taylor and Francis Online.
This paper discusses key issues and highlighted topics in thermal hydraulics in connection with Japan's current sodium-cooled fast reactor development efforts, with particular focus on design study and related research of the Japan Sodium-Cooled Fast Reactor (JSFR). Several innovative technologies, i.e., compact reactor vessel, two-loop system, full natural-circulation decay heat removal, and recriticality-free core, have been investigated to reduce construction cost and to achieve a high level of reactor safety. Preliminary evaluations of innovative technologies to be applied to JSFR are ongoing. In this paper, the progress of design study is reviewed, and key issues are discussed. Then, research and development activities on the thermal hydraulics are highlighted in connection with the phenomena taking place in natural-circulation decay heat removal and innovative design and enhanced safety features.